U.S. Nuclear Regulatory Commission Operations Center Event Reports For 09/05/97 - 09/08/97 ** EVENT NUMBERS ** 32749 32874 32875 32876 32877 32878 32879 32880 32881 32882 32883 32884 !!!!!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!!! +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32749 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 08/12/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 16:10 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 08/12/97 | +------------------------------------------------+EVENT TIME: 14:08[CDT]| |NRC NOTIFIED BY: JOHN CARLSON |LAST UPDATE DATE: 09/05/97 | |HQ OPS OFFICER: DOUG WEAVER +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JOSEPH TAPIA RDO | |AUNA 50.72(b)(1)(ii)(A) UNANALYZED COND OP | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 98 POWER OPERATION | 98 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | POLAR CRANE USED DURING POWER OPERATIONS - NOT ALLOWED BY UFSAR | | | | THE LICENSEE HAS DETERMINED THAT USE OF THE POLAR CRANE DURING CONDITIONS | | OTHER THAN COLD SHUTDOWN IS NOT ALLOWED. SINCE THE POLAR CRANE HAS BEEN | | USED DURING CYCLE SEVEN ON SEVERAL OCCASIONS, THE LICENSEE IS REPORTING | | THIS AS AN UNANALYZED CONDITION. | | | | THIS ISSUE STEMS FROM THE FACT THAT THE POLAR CRANE IS POWERED BY A | | 480-VOLT SAFETY-RELATED ELECTRICAL BUS. HOWEVER, THE ELECTRICAL PROTECTIVE | | DEVICES ASSOCIATED WITH THE POLAR CRANE ARE NOT SUFFICIENT TO ENSURE THE | | VIABILITY OF THE SAFETY-RELATED POWER SUPPLY IN CASE OF A FAULT ON THE | | POLAR CRANE. THE LICENSEE HAS ELECTRICALLY ISOLATED THE POLAR CRANE | | PENDING RESOLUTION OF THIS ISSUE. | | | | THE LICENSEE PLANS TO INFORM THE NRC RESIDENT INSPECTOR. | | | | * * * UPDATE AT 1739 ON 9/5/97 FROM CARLSON TAKEN BY STRANSKY * * * | | | | THE LICENSEE IS RETRACTING THIS EVENT NOTIFICATION. THE FOLLOWING IS TEXT | | FROM A FACSIMILE SUBMITTED BY THE LICENSEE: | | | | "AFTER FURTHER EVALUATION, RIVER BEND STATION HAS DETERMINED THAT THE | | DEFICIENCY DID NOT RESULT IN THE NUCLEAR POWER PLANT BEING IN AN UNANALYZED | | CONDITION THAT SIGNIFICANTLY COMPROMISED PLANT SAFETY. ASSUMING THE | | NON-SAFETY LOAD (THE POLAR CRANE MOTOR) FAULTED AS A PRECONDITION AND THE | | SAFETY-RELATED SUPPLY BREAKER (22) TO THAT LOAD FAILING CLOSED AS THE | | SINGLE ASSUMED FAULT, THE 480[-VOLT] EJS-SWG2A BUS SUPPLY BREAKER (38) | | STILL EXISTS TO ISOLATE THE BUS FROM THE REST OF THE ELECTRICAL SYSTEM. THE | | DIVISION II AND III ELECTRICAL BUSSES AS WELL AS THE OTHER DIVISION I | | 480-VOLT ELECTRICAL BUS AND THE DIVISION I 4160-VOLT ELECTRICAL BUS WOULD | | BE UNAFFECTED BY THIS CONDITION AND WOULD BE AVAILABLE. THE PLANT LEVEL | | SAFETY ANALYSIS DESIGN BASIS EVENT ALLOWS FOR THE LOSS OF ONE COMPLETE | | SAFETY-RELATED ELECTRICAL DIVISION. THIS EVENT WOULD AFFECT ONLY ONE BUS | | OF ONE DIVISION. THEREFORE, THE CONDITION DESCRIBED IN THIS CR WAS WITHIN | | ANALYZED CONDITIONS AND DID NOT SIGNIFICANTLY IMPACT PLANT SAFETY." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |FUEL CYCLE FACILITY | |EVENT NUMBER: 32874 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: GE NUCLEAR ENERGY |NOTIFICATION DATE: 09/05/97 | | RXTYPE: URANIUM FUEL FABRICATION |NOTIFICATION TIME: 08:56 [ET]| |COMMENTS: LEU CONVERSION (UF6 TO UO2) |EVENT DATE: 09/04/97 | | LEU FABRICATION |EVENT TIME: 14:33[EDT]| | LWR COMMERICAL FUEL |LAST UPDATE DATE: 09/05/97 | | CITY: WILMINGTON REGION: 2 +-----------------------------+ | COUNTY: NEW HANOVER STATE: NC |PERSON ORGANIZATION| |LICENSE#: SNM-1097 AGREEMENT: Y |WILLIAM RANKIN RDO | | DOCKET: 07001113 |DON COOL/NMSS EO | +------------------------------------------------+RICHARD BARRETT/AEOD IRD | |NRC NOTIFIED BY: LON E. PAULSON | | |HQ OPS OFFICER: LEIGH TROCINE | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |KBBF 70.50(b)(2)(ii) EQUIP DISABLED/FAILS | | |NBNL RESPONSE-BULLETIN | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RELEASE OF 31.5 ęCi OF LOW ENRICHED URANIUM (2% ENRICHED URANIUM - | | PARTICULATE UO2F2) FROM THE DRY CONVERSION PROCESS HF RECOVERY PROCESS | | EXHAUST STACK | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "AT APPROXIMATELY 1425 ON SEPTEMBER 4, 1997, A SMALL RELEASE OF URANIUM | | FROM THE DRY CONVERSION PROCESS (DCP) HF RECOVERY PROCESS EXHAUST STACK WAS | | DETECTED VIA NORMAL SAMPLING. THE OFF-NORMAL SITUATION WAS DECLARED [AS] | | AN UNUSUAL EVENT PER INTERNAL PROCEDURES AT 1440 [HOURS]." | | | | "THERE WERE NO INJURIES[, AND THERE WAS NO] DETECTABLE EXPOSURE TO WORKERS | | OR TO THE PUBLIC. AIR SAMPLES AT SITE BOUNDARIES INDICATED NO DETECTABLE | | ACTIVITY ABOVE BACKGROUND. THE INITIAL STACK SAMPLE INDICATED [THAT] 22.8 | | GRAMS OF URANIUM WERE RELEASED. A SAMPLE TAKEN TWO HOURS LATER INDICATED | | THE RELEASE HAD BEEN MITIGATED. NO STANDARDS OR REGULATORY LIMITS WERE | | EXCEEDED. STACK SAMPLING IS CONTINUING AT AN ELEVATED FREQUENCY." | | | | "THE CAUSE OF THE RELEASE APPEARS TO BE ASSOCIATED WITH RESTART ACTIVITIES | | OF DCP LINE 1. LINE 1 WAS DOWN DUE TO PLUGGAGE IN THE FEED LINE TO THE | | CONVERSION KILN. AN INVESTIGATION IS UNDERWAY TO DETERMINE THE EXACT | | RELEASE MECHANISM." | | | | "[THE LICENSEE IS] REPORTING THIS CONDITION PURSUANT TO 10 CFR 70.50(b)(2). | | THIS REPORT IS REQUIRED WITHIN 24 HOURS. DCP CONVERSION ACTIVITIES HAVE | | BEEN SHUT DOWN PENDING ROOT CAUSE DETERMINATION AND CORRECTIVE ACTIONS." | | | | THE LICENSEE PLANS TO NOTIFY THE STATE AND LOCAL AUTHORITIES AND THE NRC | | REGION 2 OFFICE. (REFER TO THE HOO LOG FOR A SITE CONTACT TELEPHONE | | NUMBER.) | | | | HOO NOTE: THE LICENSEE'S UNUSUAL EVENT DECLARATION WAS BASED ON INTERNAL | | PROCEDURES, AND IT IS CONSIDERED BY THE LICENSEE TO BE AN | | INTERNAL (OR OFF-NORMAL) CLASSIFICATION ONLY. THE LICENSEE DOES | | NOT CONSIDER THIS TO BE TO BE AN EMERGENCY CLASSIFICATION. | | | | * * * UPDATE AT 1433 ON 9/5/97 FROM PAULSON TAKEN BY STRANSKY * * * | | | | THE LICENSEE UPDATED ITS INITIAL REPORT TO NOTE THAT THIS EVENT IS ALSO | | REPORTABLE UNDER THE REQUIREMENTS OF NRC BULLETIN 91-01 (24-HOUR REPORT). | | THE LICENSEE CLASSIFIED THE EVENT AS HAVING LOW SAFETY SIGNIFICANCE BECAUSE | | IT INVOLVED 100-GRAM QUANTITIES IN UNFAVORABLE GEOMETRY VESSELS. THE TOTAL | | AMOUNT OF MATERIAL WAS LESS THAN 150 GRAMS OF URANIUM ENRICHED TO 2% BY | | WEIGHT). CONTROLLED PARAMETERS WERE MASS (LIMITED BY PHYSICAL BARRIERS AND | | PROCESS FLOW CONTROLS) AND GEOMETRY (THE HF CONDENSER AND VAPOR/LIQUID | | SEPARATOR). | | | | THE HOO NOTIFIED THE R2DO (RANKIN) AND NMSS EO (COOL). | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32875 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: COOK REGION: 3 |NOTIFICATION DATE: 09/05/97 | |UNIT: [1] [2] [ ] STATE: MI |NOTIFICATION TIME: 09:21 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/05/97 | +------------------------------------------------+EVENT TIME: 08:56[EDT]| |NRC NOTIFIED BY: RANDY PTACEK |LAST UPDATE DATE: 09/05/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |AOUT 50.72(b)(1)(ii)(B) OUTSIDE DESIGN BASIS | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | FAILURE TO MAINTAIN THE CONTAINMENT RECIRCULATION SUMP 1/4" PARTICULATE | | RETENTION REQUIREMENT (HISTORICAL ISSUE) | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "A 1/4" PARTICULATE RETENTION REQUIREMENT FOR THE CONTAINMENT RECIRCULATION | | SUMP WAS NOT PROPERLY ESTABLISHED IN 1979 FOLLOWING SUMP MODIFICATIONS. THE | | CONTAINMENT RECIRCULATION SUMP REQUIREMENT TO RETAIN 1/4" PARTICLES IS TO | | ENSURE THAT CONTAINMENT SPRAY NOZZLES DO NOT BECOME PLUGGED. THE | | CONTAINMENT SPRAY SYSTEM TAKES SUCTION FROM THE CONTAINMENT RECIRCULATION | | SUMP FOLLOWING INJECTION OF THE REFUELING WATER STORAGE TANK SUPPLY DURING | | A LOSS OF COOLANT ACCIDENT." | | | | "IN 1979, MODIFICATIONS WERE PERFORMED ON THE CONTAINMENT RECIRCULATION | | SUMP. ONE OF THE MODIFICATIONS INVOLVED MOVING A 1/4" RETENTION ELEMENT | | FROM INSIDE THE RECIRCULATION SUMP TO THE ENTRANCE OF THE SUMP. WHEN THE | | RETENTION ELEMENT WAS MOVED, THE 1/4" RETENTION REQUIREMENT WAS NOT FULLY | | ADDRESSED, AND PATHWAYS EXCEEDING THE 1/4" REQUIREMENT WERE INADVERTENTLY | | ESTABLISHED. THE INADVERTENT PATHWAYS ESTABLISHED INCLUDED: 3/4" VENTS IN | | THE ROOF OF THE RECIRCULATION SUMP ENTRANCE, THE CONTAINMENT SUMP DRAIN | | LINE FROM THE RECIRCULATION SUMP, AND SMALL GAPS AROUND THE SUMP ENTRANCE. | | THESE PATHWAYS HAVE SINCE BEEN ELIMINATED OR THE 1/4" REQUIREMENT HAS BEEN | | ESTABLISHED." | | | | "[THE LICENSEE IS] REPORTING THE FACT THAT SINCE 1979 UNTIL THE 1/4" | | REQUIREMENT WAS ESTABLISHED OR THE PATHWAY WAS ELIMINATED, THE CONTAINMENT | | RECIRCULATION SUMP DID NOT MEET ITS DESIGN REQUIREMENT." | | | | "[THE] CONTAINMENT RECIRCULATION SUMP CURRENTLY MEETS [THE] 1/4" | | REQUIREMENT. A CONDITION REPORT HAS BEEN WRITTEN TO INITIATE INVESTIGATION | | INTO THIS EVENT AND DETERMINE APPROPRIATE PREVENTIVE ACTIONS." | | | | THIS EVENT WAS DETERMINED TO BE REPORTABLE AT 0856 ON SEPTEMBER 5, 1997. | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32876 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: RIVER BEND REGION: 4 |NOTIFICATION DATE: 09/05/97 | |UNIT: [1] [ ] [ ] STATE: LA |NOTIFICATION TIME: 11:12 [ET]| |RX TYPE: [1] GE-6 |EVENT DATE: 09/05/97 | +------------------------------------------------+EVENT TIME: 09:30[CDT]| |NRC NOTIFIED BY: VERNON CARLSON |LAST UPDATE DATE: 09/05/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: | | |DDDD 73.71 UNSPECIFIED PARAGRAPH | | | |BLAINE MURRAY, REG 4 IAT | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 90 POWER OPERATION | 90 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DISCOVERY OF EMPLOYMENT HISTORY FALSIFICATION BY A CONTRACTOR | | | | DURING A NORMAL BACKGROUND SEARCH, IT WAS DISCOVERED THAT A CONTRACTOR | | EMPLOYEE FALSIFIED HIS EMPLOYMENT HISTORY DOCUMENTATION. WHEN THIS | | INFORMATION WAS RECEIVED, THE EMPLOYEE'S ACCESS WAS IMMEDIATELY TERMINATED, | | AND HIS KEY CARD WAS DELETED. (REFER TO THE HOO LOG FOR ADDITIONAL | | DETAILS.) | | | | THE LICENSEE NOTIFIED THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32877 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: NUCOR STEEL CORPORATION |NOTIFICATION DATE: 09/05/97 | | CITY: NORFOLK REGION: 4 |NOTIFICATION TIME: 16:16 [ET]| | COUNTY: STATE: NE |EVENT DATE: 09/03/97 | |LICENSE#: AGREEMENT: Y |EVENT TIME: 07:30[CDT]| | DOCKET: |LAST UPDATE DATE: 09/05/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |GENE BATES RDO | | | | +------------------------------------------------+ | |NRC NOTIFIED BY: B. HEARTY | | |HQ OPS OFFICER: BOB STRANSKY | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NAGR AGREEMENT STATE | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | AGREEMENT STATE REPORT | | | | THE FOLLOWING IS TEXT OF A FACSIMILE SUBMITTED BY THE NEBRASKA DEPARTMENT | | OF HEALTH AND HUMAN SERVICES: | | | | "NUCOR CORPORATION, DOING BUSINESS AS NUCOR STEEL CORPORATION, A METAL | | RECYCLING FACILITY LICENSED TO USE FIXED GAUGES FOR MONITORING LEVELS IN A | | MELT/CAST MOLD, FAILED IN AN ATTEMPT TO CLOSE A SHUTTER ON A RECENTLY | | INSTALLED LEVEL GAUGE. JENDCO CORPORATION WAS CONTRACTED BY NUCOR AND | | INSTALLED FOUR NEW BERTHOLD LB-300 ML LEVEL GAUGES IN MID AUGUST 1997. THE | | GAUGE SHUTTERS ARE OPENED AND CLOSED MANUALLY BY TURNING A SQUARE LUG ON | | THE TOP OF THE GAUGE. NUCOR WAS PERFORMING PREOPERATIONAL CHECKS ON 9/3/97 | | WHEN ONE GAUGE'S SHUTTER WOULD NOT MOVE TO THE FULLY CLOSED POSITION WHEN | | APPLYING NORMAL TENSION TO THE SHUTTER CONTROL LUG. THE LICENSEE DID NOT | | ATTEMPT TO FORCE THE SHUTTER CLOSED, SECURED THE AREA AROUND THE GAUGE, AND | | CALLED JENDCO FOR ASSISTANCE. A JENDCO SERVICE ENGINEER ARRIVED THAT | | EVENING AND DETERMINED THAT A SCREW WAS INTERFERING WITH THE OPERATION OF | | THE SHUTTER. THE SCREW WAS ADJUSTED BY THE SERVICE ENGINEER, AND THE | | SHUTTER WAS MOVED TO THE CLOSED POSITION. SINCE THE GAUGES ARE NORMALLY | | MAINTAINED IN THE OPEN POSITION AND NO UNUSUAL AMOUNT OF TIME WAS SPENT BY | | LICENSEE PERSONNEL IN THE VICINITY OF THE GAUGE, IT IS ASSUMED THAT NO | | SIGNIFICANT EXPOSURE WAS RECEIVED. THE INDIVIDUALS ATTEMPTING TO CLOSE THE | | SHUTTER WERE MONITORED WITH FILM BADGES, AND THE LICENSEE HAS BEEN ASKED TO | | REPORT THE DOSES RECEIVED WITH THE REQUIRED WRITTEN REPORT." | | | | THE GAUGE CONTAINS A 0.017-Ci Co-60 SOURCE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32878 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: DRESDEN REGION: 3 |NOTIFICATION DATE: 09/05/97 | |UNIT: [ ] [ ] [3] STATE: IL |NOTIFICATION TIME: 17:21 [ET]| |RX TYPE: [1] GE-1,[2] GE-3,[3] GE-3 |EVENT DATE: 09/05/97 | +------------------------------------------------+EVENT TIME: 14:49[CDT]| |NRC NOTIFIED BY: B. SAMPSON |LAST UPDATE DATE: 09/05/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |AIND 50.72(b)(2)(iii)(D) ACCIDENT MITIGATION | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | | | | | 3 | N Y 99 POWER OPERATION | 99 POWER OPERATION | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | HPCI SYSTEM DECLARED INOPERABLE | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "WHILE PERFORMING A NORMALLY SCHEDULED HIGH PRESSURE COOLANT INJECTION | | (HPCI) QUARTERLY SURVEILLANCE, TWO ANNUNCIATORS ALARMED WHICH ALERTED THE | | OPERATING CREW [THAT] CONDITIONS WERE NOT NORMAL. THE FIRST WAS GLAND SEAL | | CONDENSER HOTWELL LEVEL HIGH. THE SECOND WAS GLAND SEAL DRAIN PRESSURE | | HIGH. A HIGH LEVEL WAS OBSERVED ON THE LOCAL SIGHT GLASS AND CONFIRMED ON | | THE SEQUENCE OF EVENTS RECORDER (SER) DISPLAY. THE GLAND SEAL LEAKOFF | | BLOWER WAS OBSERVED TO BE OFF, AND LATER INSPECTION OF THE BREAKER | | DETERMINED THE BLOWER HAD TRIPPED. BASED ON THE CONDITIONS OBSERVED AND | | LESSONS LEARNED FROM OTHER INDUSTRY EVENTS, THE UNIT SUPERVISOR ORDERED THE | | ROOM BE CLEARED OF PERSONNEL AND THE HPCI TURBINE TRIPPED. HPCI WAS | | DECLARED INOPERABLE, AND MAINTENANCE AS WELL AS COMPONENT ENGINEERS WERE | | SUMMONED FOR TROUBLESHOOTING. THE UNIT IS IN A 14-DAY [LIMITING CONDITION | | FOR OPERATION], AS OTHER REQUIRED [EMERGENCY CORE COOLING] SYSTEMS ARE | | STILL AVAILABLE." | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED BY THE LICENSEE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32879 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: FITZPATRICK REGION: 1 |NOTIFICATION DATE: 09/05/97 | |UNIT: [1] [ ] [ ] STATE: NY |NOTIFICATION TIME: 19:33 [ET]| |RX TYPE: [1] GE-4 |EVENT DATE: 09/05/97 | +------------------------------------------------+EVENT TIME: 17:24[EDT]| |NRC NOTIFIED BY: TOBY TORBITT |LAST UPDATE DATE: 09/05/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |LAWRENCE DOERFLEIN RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | RADWASTE BUILDING VENTILATION ISOLATION | | | | WHILE PERFORMING A CALIBRATION OF THE 'B' RADWASTE BUILDING VENTILATION | | RADIATION MONITOR (17RM-458B), THE RADWASTE BUILDING VENTILATION SYSTEM | | ISOLATED. THE RADIATION MONITOR HAD NOT BEEN PROPERLY REMOVED FROM SERVICE, | | AND THE ISOLATION OCCURRED WHEN THE CHECK SOURCE WAS INSERTED INTO THE | | DETECTOR. THE LICENSEE COMPLETED THE TEST PROCEDURE AND HAS RESET THE | | VENTILATION ISOLATION. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32880 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: POINT BEACH REGION: 3 |NOTIFICATION DATE: 09/05/97 | |UNIT: [ ] [2] [ ] STATE: WI |NOTIFICATION TIME: 21:27 [ET]| |RX TYPE: [1] W-2-LP,[2] W-2-LP |EVENT DATE: 09/05/97 | +------------------------------------------------+EVENT TIME: 20:22[CDT]| |NRC NOTIFIED BY: JOHN JAECKLE |LAST UPDATE DATE: 09/05/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |JAMES CREED RDO | |ASHU 50.72(b)(1)(i)(A) PLANT S/D REQD BY TS | | |NLCO TECH SPEC LCO A/S | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N Y 100 POWER OPERATION | 100 POWER OPERATION | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | TECHNICAL SPECIFICATION REQUIRED SHUTDOWN | | | | THE LICENSEE COMMENCED A UNIT SHUTDOWN FROM 100% POWER IN ACCORDANCE WITH | | PLANT TECHNICAL SPECIFICATION 15.3.3.D.2.a AFTER CONCLUDING THAT THE ISSUE | | THAT PLACED THE UNIT INTO THE LIMITING CONDITION FOR OPERATION WOULD NOT BE | | RESOLVED BEFORE THE TIME CLOCK EXPIRED. ON 9/3/97, THE LICENSEE IDENTIFIED | | THAT AN UNDERVOLTAGE CONDITION COULD OCCUR DURING CERTAIN LOSS OF COOLANT | | ACCIDENT/LOSS OF OFFSITE POWER SCENARIOS IF A SERVICE WATER PUMP AND | | CONTAINMENT SPRAY PUMP WERE TO START AT THE SAME TIME WHILE THEIR | | ELECTRICAL BUS WAS BEING SUPPLIED BY THE 'G01' EMERGENCY DIESEL GENERATOR. | | (REFER TO RELATED EVENT NUMBER 32865.) THE LICENSEE PLANS TO TAKE THE UNIT | | TO COLD SHUTDOWN UNTIL THIS ISSUE IS RESOLVED. | | | | A PRESS RELEASE WILL BE MADE BY THE LICENSEE. THE NRC RESIDENT INSPECTOR | | HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |GENERAL INFORMATION or OTHER | |EVENT NUMBER: 32881 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |LICENSEE: ANCO TESTING |NOTIFICATION DATE: 09/06/97 | | CITY: ST LOUIS REGION: 3 |NOTIFICATION TIME: 02:49 [ET]| | COUNTY: STATE: MO |EVENT DATE: 09/05/97 | |LICENSE#: 24-24459-01 AGREEMENT: N |EVENT TIME: 12:45[CDT]| | DOCKET: |LAST UPDATE DATE: 09/06/97 | | +-----------------------------+ | |PERSON ORGANIZATION| | |JAMES CREED RDO | | |ROBERT PIERSON, NMSS EO | +------------------------------------------------+ | |NRC NOTIFIED BY: COLE | | |HQ OPS OFFICER: CHAUNCEY GOULD | | +------------------------------------------------+ | |EMERGENCY CLASS: NOT APPLICABLE | | |10 CFR SECTION: | | |NINF INFORMATION ONLY | | | | | | | | | | | | | | +------------------------------------------------+-----------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DENSITY GAUGE RUN OVER BY A CAR IN ST. LOUIS, MO. | | | | THE LICENSEE REPORTED THAT A DENSITY GAUGE WAS RUN OVER BY A CAR WHILE ROAD | | WORK WAS BEING PERFORMED ON THE CENTER LANE OF I-70 WEST BOUND 3/4 MILES | | WEST OF KINGS HIGHWAY IN ST. LOUIS, MO. THE SOURCE HANDLE WAS PULLED OUT | | OF THE DEVICE, AND THE SOURCES ARE CURRENTLY UNSHIELDED LAYING ON THE | | ASPHALT PAVEMENT. THE CAMBELL MC3 GAUGE CONTAINED CS-137 (10 MILLICURIES) | | AND AM-241 (50 MILLICURIES). THE SOURCES ARE SEALED AND APPEAR NOT TO HAVE | | BEEN COMPROMISED. THE AREA HAS BEEN ROPED OFF, AND NO PERSONNEL APPEAR TO | | HAVE BEEN EXPOSED. THE FIRE DEPARTMENT HAZMAT TEAM IS ON THE WAY TO THE | | SITE. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32882 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: TROJAN REGION: 4 |NOTIFICATION DATE: 09/06/97 | |UNIT: [1] [ ] [ ] STATE: OR |NOTIFICATION TIME: 16:47 [ET]| |RX TYPE: [1] W-4-LP |EVENT DATE: 09/06/97 | +------------------------------------------------+EVENT TIME: 12:18[PDT]| |NRC NOTIFIED BY: GERALD PERRIN |LAST UPDATE DATE: 09/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES RDO | |APRE 50.72(b)(2)(vi) OFFSITE NOTIFICATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | N N 0 REFUELING | 0 REFUELING | | | | | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | NOTIFICATION TO STATE REGARDING VIOLATION OF NPDES DISCHARGE LIMIT | | | | THE LICENSEE NOTIFIED THE OREGON STATE DEPARTMENT OF THE ENVIRONMENT | | REGARDING THE VIOLATION OF AN NATIONAL POLLUTION DISCHARGE ELIMINATION | | SYSTEM (NPDES) LIMIT. WHILE RINSING SODIUM BISULFITE BARRELS AFTER | | REFILLING A TANK, THE LICENSEE RECEIVED A pH ALARM. THE MINIMUM pH MEASURED | | AT OUTFALL #1 TO THE COLUMBIA RIVER WAS 5.6 ACCORDING TO THE RECORDER, AND | | 5.3 BASED ON A GRAB SAMPLE. THE LOWER LIMIT IS 6.0. THE LICENSEE WAS ABLE | | TO RECOVER pH AT THE OUTFALL TO ABOVE THE LOWER LIMIT WITHIN 10 MINUTES. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32883 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: MCGUIRE REGION: 2 |NOTIFICATION DATE: 09/06/97 | |UNIT: [1] [2] [ ] STATE: NC |NOTIFICATION TIME: 23:20 [ET]| |RX TYPE: [1] W-4-LP,[2] W-4-LP |EVENT DATE: 09/06/97 | +------------------------------------------------+EVENT TIME: 21:45[EDT]| |NRC NOTIFIED BY: RANDY TRACEY |LAST UPDATE DATE: 09/06/97 | |HQ OPS OFFICER: BOB STRANSKY +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |CAUDLE JULIAN RDO | |ARPS 50.72(b)(2)(ii) RPS ACTUATION | | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | 1 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | 2 | A/R Y 100 POWER OPERATION | 0 HOT STANDBY | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | DUAL UNIT REACTOR TRIP DUE TO LOSS OF NONSAFETY INSTRUMENT BUS | | | | AT 2145, BOTH UNITS TRIPPED FROM 100% POWER WHEN NONSAFETY 120-VAC | | INSTRUMENT BUS 'KXA' TRIPPED. LOSS OF THE 'KXA' BUS GENERATED A NONSAFETY | | TRIP SIGNAL TO THE UNIT 1 MAIN FEEDWATER PUMPS AND A NONSAFETY CLOSURE | | SIGNAL TO THE UNIT 2 MAIN STEAM ISOLATION VALVES. THE TRIPS OF BOTH UNITS | | WERE UNCOMPLICATED WITH ALL CONTROL RODS INSERTING COMPLETELY AND THE | | AUXILIARY FEEDWATER SYSTEMS FOR BOTH UNITS STARTING TO PROVIDE STEAM | | GENERATOR (S/G) LEVEL CONTROL. INITIALLY FOLLOWING THE TRIPS, STEAM FROM | | BOTH UNITS WAS BEING RELIEVED VIA THE S/G ATMOSPHERIC POWER OPERATED RELIEF | | VALVES (PORV). | | | | AT 2300, POWER WAS RESTORED TO THE 'KXA' BUS, AND S/G PRESSURE FOR UNIT 1 | | IS NOW BEING CONTROLLED BY THE MAIN CONDENSER STEAM DUMPS. THE LICENSEE IS | | CURRENTLY IN THE PROCESS OF CLEARING THE MAIN STEAM ISOLATION SIGNAL AND | | REPRESSURIZING THE MAIN STEAM HEADER IN PREPARATION FOR PLACING THE UNIT 2 | | MAIN CONDENSER STEAM DUMPS INTO SERVICE. THE LICENSEE IS INVESTIGATING THE | | CAUSE OF THE LOSS OF THE 'KXA' INSTRUMENT BUS. | | | | THE NRC RESIDENT INSPECTOR HAS BEEN INFORMED. | +------------------------------------------------------------------------------+ +----------------------------------+ +-----------------------+ |POWER REACTOR | |EVENT NUMBER: 32884 | +----------------------------------+ +-----------------------+ +------------------------------------------------+-----------------------------+ |FACILITY: PALO VERDE REGION: 4 |NOTIFICATION DATE: 09/08/97 | |UNIT: [ ] [2] [ ] STATE: AZ |NOTIFICATION TIME: 02:21 [ET]| |RX TYPE: [1] CE,[2] CE,[3] CE |EVENT DATE: 09/07/97 | +------------------------------------------------+EVENT TIME: 19:23[MST]| |NRC NOTIFIED BY: DAN MARKS |LAST UPDATE DATE: 09/08/97 | |HQ OPS OFFICER: LEIGH TROCINE +-----------------------------+ +------------------------------------------------+ NOTIFICATIONS | |EMERGENCY CLASS: NOT APPLICABLE +-----------------------------+ |10 CFR SECTION: |GENE BATES RDO | |AESF 50.72(b)(2)(ii) ESF ACTUATION | | | | | | | | | | | | | | +-----+----------+-------+--------+--------------+--+--------+-----------------+ |UNIT |SCRAM CODE|RX CRIT|INIT PWR| INIT RX MODE |CURR PWR| CURR RX MODE | +-----+----------+-------+--------+-----------------+--------+-----------------+ | | | | | 2 | N N 0 COLD SHUTDOWN | 0 COLD SHUTDOWN | | | | | +-----+---------------------------------------------+--------------------------+ EVENT TEXT +------------------------------------------------------------------------------+ | INADVERTENT ENGINEERED SAFETY FEATURE (ESF) ACTUATION DUE TO AN INCORRECTLY | | PERFORMED STEP DURING THE PERFORMANCE OF SURVEILLANCE TESTING | | | | THE FOLLOWING TEXT IS A PORTION OF A FACSIMILE RECEIVED FROM THE LICENSEE: | | | | "[AN] INADVERTENT ESF ACTUATION RESULTED FROM AN INCORRECTLY PERFORMED STEP | | DURING THE PERFORMANCE OF [AN] INTEGRATED SAFEGUARDS SURVEILLANCE TEST ON | | THE 'B' SAFETY EQUIPMENT." | | | | "THE SUB-SECTION OF THE TEST BEING PERFORMED IS A LOSS OF POWER (LOP) TO | | TRAIN 'B' INITIATED BY OPENING THE NORMAL SUPPLY BREAKER TO E-NBN-X04. THE | | INTENT IS TO DEMONSTRATE PROPER RESPONSE OF THE ESF EQUIPMENT. THE | | [EMERGENCY DIESEL GENERATOR (EDG)] IS INITIALLY PLACED IN AN 'OVERRIDE' | | CONDITION PRIOR TO THE 'LOP' INITIATION TO DEMONSTRATE THAT UPON THE | | RESULTING 'LOAD SHED' SIGNAL, THE EDG WILL BE REMOVED FROM 'OVERRIDE' AND | | WILL START IN THE 'EMERGENCY' MODE. ONE OF THE PRE-TEST CONDITIONS IS TO | | PLACE THE CLASS BUS ALTERNATE SUPPLY BREAKER IN THE 'TEST' POSITION AND | | CLOSED LOCALLY. DUE TO AN INCORRECTLY PERFORMED STEP, THE ALTERNATE SUPPLY | | BREAKER WAS CLOSED FROM THE CONTROL ROOM. THE SYNCHRONIZING SWITCH | | INTERLOCK LOGIC AUTOMATICALLY OPENED THE NORMAL SUPPLY BREAKER RESULTING IN | | A 'LOP' ON THE CLASS BUS. THE DIESEL GENERATOR STARTED AND RESTORED BUS | | VOLTAGE. ALL EQUIPMENT OPERATED AS REQUIRED. THERE WERE NO OTHER | | ACTUATIONS, AND NONE WERE REQUIRED." | | | | "THE EVENT DID NOT RESULT IN ANY CHALLENGES TO THE FISSION PRODUCT BARRIER | | OR RESULT IN ANY RELEASES OF RADIOACTIVE MATERIALS. THERE WERE NO ADVERSE | | CONSEQUENCES OR IMPLICATIONS AS A RESULT OF THIS EVENT. THIS EVENT DID NOT | | ADVERSELY AFFECT THE SAFE OPERATION OF THE PLANT OR HEALTH AND SAFETY OF | | THE PUBLIC." | | | | THE LICENSEE PLANS TO NOTIFY THE NRC RESIDENT INSPECTOR. | +------------------------------------------------------------------------------+